Temperature and heat flux calculations for the maximum power channel of the TRIGA IAN-R1 research reactor

Revista Investigaciones y Aplicaciones Nucleares

José Antonio Sarta¹  Luis Álvaro Castiblanco² 

[1] Pontificia Universidad Javeriana;Technology and Nuclear Science TNSc.;

关键词: temperature;    heat flux;    departure from nucleate boiling;   

DOI  :  https://doi.org/10.32685/2590-7468/invapnuclear.3.2019.509

来源: DOAJ

【 摘 要 】

With cooperation of the International Atomic Energy Agency (IAEA), thermal-hydraulic calculations were carried out for conversion of the IAN-R1 Reactor from MTR-HEU fuel to TRIGA-LEU fuel. To establish thermal-hydraulic calculation and analysis research in Colombia, this program was carried out and included training, acquisition of hardware, software and natural convection flow calculations for the TRIGA IAN-R1 research reactor operating at 100 kW. The purpose of the study is to validate the steady state thermal hydraulic analysis that has been carried out by means of the NATCON code. This paper presents the results of the maximum axial temperature distribution for fuel, clad, and coolant. In addition, the Bernath critical heat flux with pool water temperature as a parameter is presented.

【 授权许可】

Unknown